Add to ORKGUnderstanding the quench front propagation during bottom core reflooding is crucial for the effective cooling during the LOCA accident. The results presented in this paper were obtained on an experimental loop with an annular test section. The test section consists of a vertical electrically heated stainless steel tube with outer diameter 9 mm and length of 1.7 m. The heated tube is placed inside a glass tube with the inner diameter 14.5 mm. Water mass flux during the reflooding is in the range from 100 kg.m−2.s−1 up to 140 kg.m−2.s−1 and the initial wall temperature of the stainless steel tube is in the range from 250 °C up to 800 °C. The presented results show the influence of the initial conditions on the quench front propagation and the...
To simulate the thermohydraulic characteristics of reflooding process of a nuclear core reactor dur...
The design, analysis and control of many metallurgical and materials operations hinges, in part, on...
The paper gives an overview on the status of the QUENCH program at FZK, including complementary bund...
Rewetting of heated surfaces is important in many physical processes and has important technological...
Phenomenon of quenching of hot fuels in core during bottom reflooding following loca event is invest...
In case of severe accident in a nuclear reactor, the fuel rods may be highly damaged and oxidized an...
During a loss-of-coolant accident in a boiling water reactor, the liquid inventory drains from the ...
In nuclear reactors, the occurrence of critical heat flux leads to fuel rod overheating with clad fu...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor, parti...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
This thesis describes work relating to the reflood phase of a Large Break Loss-of-Coolant Accident (...
The paper presents the process of two-dimensional axisymmetric quenching of cylindrical samples in w...
To simulate the thermohydraulic characteristics of reflooding process of a nuclear core reactor dur...
The design, analysis and control of many metallurgical and materials operations hinges, in part, on...
The paper gives an overview on the status of the QUENCH program at FZK, including complementary bund...
Rewetting of heated surfaces is important in many physical processes and has important technological...
Phenomenon of quenching of hot fuels in core during bottom reflooding following loca event is invest...
In case of severe accident in a nuclear reactor, the fuel rods may be highly damaged and oxidized an...
During a loss-of-coolant accident in a boiling water reactor, the liquid inventory drains from the ...
In nuclear reactors, the occurrence of critical heat flux leads to fuel rod overheating with clad fu...
Study on understanding of the complexities of boiling in the narrow channel which was occured in a s...
International audienceDuring a Loss of Coolant Accident (LOCA) in a Pressurized Water Reactor, parti...
In all severe accidents scenarios the main goal of operator actions (AMM, accident management measur...
This thesis describes work relating to the reflood phase of a Large Break Loss-of-Coolant Accident (...
The paper presents the process of two-dimensional axisymmetric quenching of cylindrical samples in w...
To simulate the thermohydraulic characteristics of reflooding process of a nuclear core reactor dur...
The design, analysis and control of many metallurgical and materials operations hinges, in part, on...
The paper gives an overview on the status of the QUENCH program at FZK, including complementary bund...